US4645625A - Decontamination of a radioactive waste liquid by electrodialysis - Google Patents
Decontamination of a radioactive waste liquid by electrodialysis Download PDFInfo
- Publication number
- US4645625A US4645625A US06/675,052 US67505284A US4645625A US 4645625 A US4645625 A US 4645625A US 67505284 A US67505284 A US 67505284A US 4645625 A US4645625 A US 4645625A
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- 238000000909 electrodialysis Methods 0.000 title claims abstract description 15
- 239000007788 liquid Substances 0.000 title claims description 16
- 238000005202 decontamination Methods 0.000 title abstract description 6
- 230000003588 decontaminative effect Effects 0.000 title description 5
- 239000002901 radioactive waste Substances 0.000 title description 3
- 150000001768 cations Chemical class 0.000 claims abstract description 47
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 41
- 150000003839 salts Chemical class 0.000 claims abstract description 38
- 239000002253 acid Substances 0.000 claims abstract description 29
- 239000012528 membrane Substances 0.000 claims abstract description 29
- 230000002285 radioactive effect Effects 0.000 claims abstract description 26
- 239000002699 waste material Substances 0.000 claims abstract description 19
- 238000000034 method Methods 0.000 claims abstract description 17
- 230000008569 process Effects 0.000 claims abstract description 16
- 238000011084 recovery Methods 0.000 claims abstract description 9
- 230000002378 acidificating effect Effects 0.000 claims abstract description 7
- 238000011033 desalting Methods 0.000 claims description 28
- 238000007865 diluting Methods 0.000 claims description 28
- 150000001450 anions Chemical class 0.000 claims description 17
- 230000007935 neutral effect Effects 0.000 claims description 16
- 230000003134 recirculating effect Effects 0.000 claims description 10
- 239000010808 liquid waste Substances 0.000 claims 3
- 238000004064 recycling Methods 0.000 claims 3
- 229910052792 caesium Inorganic materials 0.000 abstract description 17
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 abstract description 15
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract description 8
- 229910017604 nitric acid Inorganic materials 0.000 abstract description 8
- 239000000243 solution Substances 0.000 description 14
- -1 salt ions Chemical class 0.000 description 10
- 150000002500 ions Chemical class 0.000 description 8
- 229910002651 NO3 Inorganic materials 0.000 description 6
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 5
- 239000012141 concentrate Substances 0.000 description 5
- 239000012267 brine Substances 0.000 description 4
- 239000001257 hydrogen Substances 0.000 description 4
- 229910052739 hydrogen Inorganic materials 0.000 description 4
- HPALAKNZSZLMCH-UHFFFAOYSA-M sodium;chloride;hydrate Chemical compound O.[Na+].[Cl-] HPALAKNZSZLMCH-UHFFFAOYSA-M 0.000 description 4
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005370 electroosmosis Methods 0.000 description 3
- 239000003456 ion exchange resin Substances 0.000 description 3
- 229920003303 ion-exchange polymer Polymers 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- GPRLSGONYQIRFK-UHFFFAOYSA-N hydron Chemical compound [H+] GPRLSGONYQIRFK-UHFFFAOYSA-N 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 238000000926 separation method Methods 0.000 description 2
- 229910052684 Cerium Inorganic materials 0.000 description 1
- YZCKVEUIGOORGS-UHFFFAOYSA-N Hydrogen atom Chemical compound [H] YZCKVEUIGOORGS-UHFFFAOYSA-N 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 239000003929 acidic solution Substances 0.000 description 1
- GWXLDORMOJMVQZ-UHFFFAOYSA-N cerium Chemical compound [Ce] GWXLDORMOJMVQZ-UHFFFAOYSA-N 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000005115 demineralization Methods 0.000 description 1
- 230000002328 demineralizing effect Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000003792 electrolyte Substances 0.000 description 1
- 239000012527 feed solution Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000011027 product recovery Methods 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000012266 salt solution Substances 0.000 description 1
- 239000002904 solvent Substances 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 229910052712 strontium Inorganic materials 0.000 description 1
- CIOAGBVUUVVLOB-UHFFFAOYSA-N strontium atom Chemical compound [Sr] CIOAGBVUUVVLOB-UHFFFAOYSA-N 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
Definitions
- This invention concerns the use of electrodialysis for the separation and concentration of ions from radioactive waste (radwaste) solutions.
- it is directed to employing a plurality of electrochemical and electrodialysis units or stacks in a novel combination to concentrate radioactive cations from low level acidic solutions that result from dissolving irradiated fuel from nuclear reactors in solvents such as nitric acid.
- the invention comprises providing a combination of various electrochemical and electrodialysis stacks, with each stack having its own specific cell configuration.
- the single drawing illustrates a flow diagram and schematic cross-sectional representation of the combination apparatus used in performing the process of the invention.
- each stack is composed of an anode and cathode electrode terminally positioned within the stack and a plurality of liquid treating chambers therebetween defined and separated from each other by ion-permeable membranes.
- the anodes and cathodes used may be any of those normally employed in electrolytic cells.
- the deacidification stack 1 as shown is made up of four compartments or chambers; i.e. an anode chamber 5 containing an anode electrode 9, two neutral chambers 6, 7 and a cathode chamber 8 with its attendant cathode electrode 10.
- the chambers are defined and separated from each other by all anion selective membranes 11 which will, in principle, only allow the passage of anions, negatively charged ions, i.e. NO 3 - toward the positive electrode 9 as shown by the direction of the arrows.
- the efficiency of the anion selective membrane 11 separating the cathode chamber 8 from adjacent chamber 7 is dependent upon the acid concentration in said adjacent chamber.
- the preferred stack design provides for the solution adjacent to the cathode chamber of the deacidification stack 1 to be of low acidity so as to enhance the net deacidification accomplished in the cathode compartment 8.
- this low acidity solution is in fact the catholyte effluent stream from the concentration stack 2 which solution is continuously deacidified in said stack 2 as it accumulates the radioactive cations, such as cesium.
- the overall acidity of the catholyte stream of the concentration stack 2 can be increased or decreased relative to the acidity of the solution passing through the cathode chamber 8 of the deacidification stack 1.
- a neutral chamber is defined herein as a chamber that neither concentrates salt nor dilutes (removes) salt therein. Because a neutral chamber is defined on both sides by membranes of the same charge i.e. both cation selective or anion selective membranes, the salt ions that pass into the chamber will also pass out of the chamber and thus there is substantially no net gain or loss of ions therein.
- the radioactive cation concentration stack 2 is of similar construction as the deacidification stack 1 in also having four chambers, i.e. anode and cathode chambers 12, 15 with their respective anode electrode 16 and cathode electrode 17, a neutral chamber 13 and a single salt diluting or separating chamber 14.
- the cation concentration stack 2 differs from the deacidification stack 1 in that a cation selective membrane 18 is placed adjacent to the cathode chamber 15 thus forming a single salt diluting (reducing) chamber 14 and allowing the cathode chamber 15 to act as a cation concentration chamber, with the cations (Cs + ) and anions (NO 3 - ) flowing in the direction of the arrows as shown.
- radioactive cations reach the catholyte stream of the concentration stack 2 only by way of the brine stream 36 from the primary desalting stack 3. Since the brine stream is also deacidified by the concentration stack 2, both hydrogen ions and the radioactive cations pass into the catholyte stream of stack 2.
- the concentration ratio of radioactive cations to acid in the brine stream 36 determines to a large extent the percent water recovery of the plant and the ultimate concentration factor for the radioactive cations. Namely, the transfer of hydrogen ions to the catholyte of the concentration stack 2 is accompanied by the transfer of water by electroosmosis. Typically, 0.1 liter of water is transferred per equivalent of hydrogen ion so that if the acid concentration entering as feed to the primary desalting stack 3 is 0.1N (0.1 equivalents/liter), then the ultimate transfer of this acid to the catholyte stream of the concentration stack 2 will carry with it 0.01 liters per liter of feed.
- the maximum water recovery (water leaving as decontaminated water out of the secondary desalting stack 4) is 99 percent and, assuming equal transfer of the radioactive cations relative to the number of equivalents per liter in the feed, the maximum concentration factor for the radioactive cations is 100.
- the water transferred to the catholyte of the concentration stack 2 with the acid is 0.05 liters per liter of feed.
- the corresponding water recovery and maximum concentration factor are 95% and 20% respectively.
- the combination, therefore, of the deacidification stack 1 (to control the acidity of the feed) and the primary desalting stack 3 is an essential feature of the process.
- Deacidification of the feed in stack 1 both improves the ratio of radioactive cations to acid (because the acid is electrochemically neutralized) and improves the ultimate concentration factor (and water recovery) of the process.
- the pair of stacks containing four chambers (or more) as described above is preferred.
- three chamber stacks consisting of a single middle chamber between the electrode chambers may be employed although not as efficiently.
- the deacidification stack 1 could use a pair of anion membranes to define a single middle chamber from the adjacent electrode chambers.
- the middle chamber of the cation concentration stack 2 could be positioned from the anode and cathode chambers by an anion and cation membrane respectively to form a single salt diluting chamber 14.
- the electrodialysis (desalting) stacks 3, 4 are shown substantially as two cell pair stacks having arrows which illustrate the direction of salt flow from the diluting stream to the salt concentrating stream.
- each stack is composed of a cathode and anode positioned respectively at each end of the stack and a plurality of alternating cation 18 and anion 11 selective membranes therebetween to form a series of alternating salt diluting (reducing) chambers and salt concentrating chambers.
- These stacks function to separate out the salts (nitric acid and radioisotopes) from the radwaste stream entering the diluting chambers and simultaneously concentrating these salts in the concentrating chambers.
- the radwaste mixture passes through desalting chambers defined between alternating cation membranes and anion membranes, held and separated in a stack arrangement by means well-known in the prior art.
- Tortuous path spacer compartments of the type disclosed in U.S. Pat. Nos. 2,708,658 and 2,891,899 can be employed to separate the membranes from each other to form alternating desalting and concentrating chambers or compartments.
- the combination of a desalting and concentrating chamber constitutes a cell pair. Any number of cell pairs can be stacked between a pair of end electrodes to produce a demineralization stack containing typically 100 cell pairs or more. Each electrical stage may in turn contain one or more hydraulic stages as is well-known in the art. Such systems are more fully described in U.S.
- ions such as nitrate (NO 3 - ) pass through the anion membranes into the waste compartments to form a salt concentrating stream.
- ions comprise the main body of the salts in the present embodiment, other ionic substances are or may also be removed in a like manner.
- a recirculating electrolyte stream is normally passed in contact with the cathode and a similar stream in contact with the anode.
- the acidic radwaste liquid to be processed is passed from a waste line 50 directly into the cathode chamber 8 of the deacidification stack 1 where substantial deacidification of the acidic waste stream occurs.
- hydrogen ions (H + ) in the cathode compartment are converted to hydrogen gas (2H + +2e - ⁇ H 2 ⁇ ) and the nitrate ions (NO 3 - ) are transferred through the neutral chambers 6, 7 via the anion membranes 11 finally ending up in the anode compartment 5.
- This passage of NO 3 - also occurs in the cation concentration stack 2 in like manner finally ending up in the anode compartment 12 as shown by the direction of the arrows.
- the nitrate ions combine with the hydrogen ions generated at the anodes (H 2 O ⁇ 2H + +1/2O 2 +2e - ) to form nitric acid.
- the acid is passed from an acid hold-up tank 20 via a common feed line 21 which splits into a separate feed line 22 going to each anode chamber.
- Make-up water is added into this recirculating anolyte stream preferably at the common feed line 21 by way of a bleed line 23 which taps-off from the line 24 carrying effluent from the neutral chambers 6, 13.
- the addition of make-up water to the anolyte recirculating stream will allow for control of the acid build-up in the hold-up tank 20.
- Acid is recovered at the desired concentration from the hold-up tank 20 by way of bleed line 25 and may be reused.
- the maximum acid content in the anolyte hold-up tank 20 is preferably maintained at about between 1-1.5 normal by control of the addition of make-up water to the recirculating anolyte loop.
- the make-up water requirement will be largely determined by the initial concentration of acid in the radwaste stream.
- the four chamber stack pair 1, 2 also share a common feed stream 26 which splits into two feed streams 27, with each stream being recycled through the neutral chambers 6, 13 into a water hold-up tank 28 to which make-up water is added via a water line 29.
- the neutral chamber 7 immediately adjacent to the cathode chamber 8 is fed with catholyte solution from a catholyte collection tank 30. From below this tank, two streams 31, 32 emerge; one stream 31, passing into and out of the neutral chamber 7 and recirculating back into the catholyte collection tank 30 via line 33. The other stream 32 recirculates back through the cathode chamber 15 of stack 2 and collects again in the catholyte tank 30 via a recirculating line 34.
- the cathode chamber 15 of the cation concentration stack 2 which is defined from the immediately adjacent single salt diluting chamber 14 by a cation selective membrane 18 functions as a cation concentrating chamber where the positively charged radioactive cations from the adjacent single diluting chamber 14 are received and collected.
- the catholyte solution is removed from the catholyte tank 30 via a bleed line 35 and prepared either for disposal or further concentration as may be required.
- the catholyte of the concentrating stack 2 will gain water due primarily to electroosmosis as the cations of H + , Cs + , etc. migrate into the cathode chamber 15.
- the electroosmotic coefficient of the hydrogen ion (H + ) is about 0.1 liters of water per equivalent of current passed.
- the coefficient is about 0.25 liters per equivalent.
- Water transport to the cathode chamber 18 can also be influenced by the relative pressure differential between the cathode chamber 15 and the adjacent salt diluting chamber 14. For example, with the cathode compartment overpressurized and at a pressure differential of 5-10 psi, water transport into the catholyte stream will determine the ultimate concentration factor of the radiosotopes.
- the present invention can process radwaste feed streams containing high acid concentrations but the product rates will be reduced if the decontaminated product water is maintained at the low 0.001 acid normality.
- the feed stream 36 to the single salt diluting chamber 14 contained therein comprises a concentrated salt solution obtained from the recirculating salt concentrate loop 37 of the primary desalting stack or unit 3.
- This single diluting compartment 14 will partially deacidify and deionize the concentrated salt stream 36 with the resulting treated stream 38 being cycled back as influent to the concentrating feed stream of the primary stack 3.
- the radwaste liquid is initially treated in the cathode chamber 8 of the deacidification stack 1 to effect partial deacidification of the waste liquid stream.
- the resulting effluent catholyte stream is thereafter passed into a hold-up tank 39 via an effluent line 51 where the release of hydrogen gas occurs. From this tank 39, two streams 40, 41 emerge.
- One stream 40 is combined with the radwaste feed stream 50 and thus recycled back through the cathode chamber 8.
- the other stream 41 passes as the dilute influent stream to the primary desalting stack 3.
- the dilute effluent stream 42 from the primary stack is then split into two streams 43, 44; one stream 43 passing as the dilute influent stream to the secondary desalting stack 4 and exiting as a deacidified and decontaminated product water stream 45.
- the other stream 44 is passed into the stack as the concentrating influent stream and removed as the effluent stream via line 46 where it is recycled back and combined with the dilute influent feed line 41 to the primary stack 3.
- This example illustrates the treatment of an acidic radwaste solution comprised of 0.27 normal nitric acid and a concentration of 0.27 ⁇ 10 -10 normal in cesium ions to result in a 100 fold reduction of cesium.
- the waste solution is fed into the cathode chamber 8 of the deacidification stack 1 at a flow rate of 289 ml. per minute.
- the pair of four chamber stacks 1, 2 each with an effective membrane area of 1,500 sq. cm. are operated at a current density of 100 ma/sq.cm.
- the primary and secondary desalting stacks 3, 4 comprise 120 and 30 cell pairs respectively, with each having two electrical stages operating at a current density of 6 and 2 ma/sq.cm. and 0.8 and 0.3 ma/sq.cm. respectively.
- Example II This example is operated in the manner of Example I using a waste solution of 0.11 normal (N) HNO 3 and 0.11 ⁇ 10 -10 normal in cesium at a flow rate of 682 ml./min.
- This example is operated in the manner of Example I on a waste solution of 0.1N acid and 0.1 ⁇ 10 -10 N cesium at a flow rate of 597 ml/min.
- the letters enclosed in circles illustrate the various points in the flow scheme where the solution is monitored.
- the following table lists the flow rates and normality of the acid and cesium concentrations at monitored points for the three examples.
- the radwaste stream, point ⁇ A is treated to recover three separate streams, i.e., (1) a concentrated nitric acid stream, point ⁇ Q , (2) a radioactive stream concentrated in cesium ions, point ⁇ P , and (3) the largest volume stream of substantially deacidified and decontaminated product water, point ⁇ Y .
- the water makeup, point ⁇ R and the dilute feed stream to the primary desalting stack 3, point ⁇ O are important as previously described above.
- the reduction in the concentration of radioactive cations, such as cesium is 100-fold from the feed (at point ⁇ A to the product (at point ⁇ Y ).
- the pH of the product is greater than 3 (i.e. acidity is less than 0.001N).
- the feed acidity ⁇ A which is relatively high (0.27N) is electrochemically neutralized in the deacidification stack 1 such that the acidity of the dilute stream feed ⁇ O to stack 3 is 0.10N.
- Make-up water ⁇ R is fed to the system at about 20% of the waste feed rate ⁇ A to stack 1 such that the acidity of the anolyte ⁇ Q increases to 1.3N.
- the cesium is concentrated in the catholyte ⁇ P of the concentration stack 2 to about 28 times the concentration of cesium in the waste feed ⁇ A to the deacidification stack 1.
- the acidity of the waste feed to the deacidification stack 1 is reduced. This allows for increased production and allows the acidity of the dilute feed stream to stack 3 to decrease.
- the cesium in the catholyte effluent from stack 2 can be concentrated to about 68 times the waste feed concentration using the same addition rate of make-up water (i.e. 60 ml/mi).
- the make-up water as a percentage of the waste feed rate is reduced to about 9% with the acidity of the anolyte maintained at about 1.3N.
- Example III the make-up water addition rate is cut to 30 ml/min, and the acidity of the anolyte ⁇ Q increases to 1.6N.
- Example II i.e. 0.10N vs. 0.11N
- Example III is less efficient (because of the higher acidity in the make-up water recirculation stream).
- Both the production and the cesium concentration factor are somewhat reduced from those under condition ⁇ B , i.e. (586 ml/min vs. 676 ml/min) and 53 times vs. 68 times, respectively.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
- Water Treatment By Electricity Or Magnetism (AREA)
Abstract
Description
TABLE
______________________________________
(SUMMARY OF RESULTS)
Point
○A
○R
○Y
○Q
○P
○O
______________________________________
(EXAMPLE I)
Flow-Ml/min. 289 60 283 56 10 288
HNO.sub.3 --Normality
0.27 -- .001 1.3 0.57 0.1
Cs.sup.+ Normality
0.27 -- 0.0027
-- 7.6 0.27
(× 10.sup.-10)
Ratio Cs.sup.+ /H.sup.+
1.0 -- 2.7 <0.01 13 2.7
(× 10.sup.-10)
(EXAMPLE II)
Flow 682 60 676 56 10 681
HNO.sub.3 0.11 -- .00044
1.3 0.57 0.044
Cesium (× 10.sup.-10)
0.11 -- .0011 -- 7.5 0.11
Ratio Cs.sup.+ /H.sup.+
1.0 -- 2.5 <0.01 13 2.5
(× 10.sup.-10)
(EXAMPLE III)
Flow 597 30 586 30 11 600
HNO.sub.3 0.1 -- .0005 1.6 0.97 0.05
Cesium (× 10.sup.-10)
0.1 -- .001 -- 5.3 0.1
Ratio Cs.sup.+ /H.sup.+
1.0 -- 1.0 <0.01 5.5 2.0
(× 10.sup.-10)
______________________________________
Claims (11)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US06/675,052 US4645625A (en) | 1984-11-26 | 1984-11-26 | Decontamination of a radioactive waste liquid by electrodialysis |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US06/675,052 US4645625A (en) | 1984-11-26 | 1984-11-26 | Decontamination of a radioactive waste liquid by electrodialysis |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US4645625A true US4645625A (en) | 1987-02-24 |
Family
ID=24708880
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US06/675,052 Expired - Fee Related US4645625A (en) | 1984-11-26 | 1984-11-26 | Decontamination of a radioactive waste liquid by electrodialysis |
Country Status (1)
| Country | Link |
|---|---|
| US (1) | US4645625A (en) |
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4740281A (en) * | 1986-10-14 | 1988-04-26 | Allied Corporation | Recovery of acids from materials comprising acid and salt |
| US5078842A (en) * | 1990-08-28 | 1992-01-07 | Electric Power Research Institute | Process for removing radioactive burden from spent nuclear reactor decontamination solutions using electrochemical ion exchange |
| US5306399A (en) * | 1992-10-23 | 1994-04-26 | Electric Power Research Institute | Electrochemical exchange anions in decontamination solutions |
| US5564104A (en) * | 1993-06-08 | 1996-10-08 | Cortex Biochem, Inc. | Methods of removing radioactively labled biological molecules from liquid radioactive waste |
| US5614077A (en) * | 1995-04-10 | 1997-03-25 | Electro-Petroleum, Inc. | Electrochemical system and method for the removal of charged species from contaminated liquid and solid wastes |
| US6103127A (en) * | 1993-06-08 | 2000-08-15 | Cortex Biochem, Inc. | Methods for removing hazardous organic molecules from liquid waste |
| RU2160473C1 (en) * | 1999-08-19 | 2000-12-10 | Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (МосНПО "Радон") | Device for demineralizing liquid radioactive wastes and non-radioactive water media |
| US20070023290A1 (en) * | 2005-07-26 | 2007-02-01 | Pionetics, Inc. | Electrochemical ion exchange with textured membranes and cartridge |
| US7959780B2 (en) | 2004-07-26 | 2011-06-14 | Emporia Capital Funding Llc | Textured ion exchange membranes |
| US8562803B2 (en) | 2005-10-06 | 2013-10-22 | Pionetics Corporation | Electrochemical ion exchange treatment of fluids |
| CN104751927A (en) * | 2013-12-26 | 2015-07-01 | 中国辐射防护研究院 | Method and system for performing electrodialysis treatment on radioactive waste incineration process waste water |
| JP2015200585A (en) * | 2014-04-09 | 2015-11-12 | 株式会社クラレ | Treating method of radioactive waste liquid |
| US9757695B2 (en) | 2015-01-03 | 2017-09-12 | Pionetics Corporation | Anti-scale electrochemical apparatus with water-splitting ion exchange membrane |
| CN113241207A (en) * | 2021-06-08 | 2021-08-10 | 中国核电工程有限公司 | Method and system for treating acidic low-level radioactive waste liquid and nuclear fuel post-treatment plant system |
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|---|---|---|---|---|
| US3296112A (en) * | 1957-07-16 | 1967-01-03 | Kollsman Paul | Method of modifying the chemical composition of substances by ion transfer |
| US3847765A (en) * | 1972-12-20 | 1974-11-12 | Mitsubishi Petrochemical Co | Method for the treatment of cyanide-containing wastes |
| US3968017A (en) * | 1974-02-13 | 1976-07-06 | Compagnia Tecnica Industrie Petroli S.P.A. | Process and an equipment for producing crystalline citric acid from solutions of alkaline citrates |
| US4324629A (en) * | 1979-06-19 | 1982-04-13 | Hitachi, Ltd. | Process for regenerating chemical copper plating solution |
-
1984
- 1984-11-26 US US06/675,052 patent/US4645625A/en not_active Expired - Fee Related
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3296112A (en) * | 1957-07-16 | 1967-01-03 | Kollsman Paul | Method of modifying the chemical composition of substances by ion transfer |
| US3847765A (en) * | 1972-12-20 | 1974-11-12 | Mitsubishi Petrochemical Co | Method for the treatment of cyanide-containing wastes |
| US3968017A (en) * | 1974-02-13 | 1976-07-06 | Compagnia Tecnica Industrie Petroli S.P.A. | Process and an equipment for producing crystalline citric acid from solutions of alkaline citrates |
| US4324629A (en) * | 1979-06-19 | 1982-04-13 | Hitachi, Ltd. | Process for regenerating chemical copper plating solution |
Cited By (22)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4740281A (en) * | 1986-10-14 | 1988-04-26 | Allied Corporation | Recovery of acids from materials comprising acid and salt |
| US5078842A (en) * | 1990-08-28 | 1992-01-07 | Electric Power Research Institute | Process for removing radioactive burden from spent nuclear reactor decontamination solutions using electrochemical ion exchange |
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